A5015790423- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Particle accelerators and beam dynamics
University of Ljubljana
2019-2021
ITER
2021
Abstract An analysis workflow has been developed to assess energy deposition and material damage for ITER vertical displacement events (VDEs) major disruptions (MD). This paper describes the use of this melt be expected during unmitigated current quench (CQ) phases VDEs MDs at different points in research plan. The plasma scenarios are modeled using DINA code with variations I p , disruption direction (upwards or downwards), Be impurity density n diffusion coefficient χ . Magnetic field line...
The beryllium (Be) main chamber wall interaction during a 5 MA/1.8 T upward, unmitigated VDE scenario, first analysed in [J. Coburn et al., Phys. Scr. T171 (2020) 014076] for ITER, has been re-evaluated using the latest energy deposition analysis software. Updates to DINA disruption model are summarized, including an improved numerical convergence 0D power balance, limitations on safety factor within plasma core, and choice maintain constant + halo poloidal cross-section. Such updates result...
Abstract On ITER, plasma start-up will be performed in limiter configuration on the inboard equatorial beryllium first wall panels (FWP). In contrast to most present tokamaks, however, this ramp-up phase comparatively long (∼10 s) and use of actively cooled components means that power flux management is key if FWP lifetime not compromised. Shaping FWPs mandatory ensure leading edges do appear between neighbouring units. For ITER panels, has been optimized account for discovery recent years...
Ion cyclotron resonance heating (ICRH) is one of the three additional schemes to be deployed on ITER. Its two antenna arrays, installed outboard midplane, will deliver 20 MW RF power in 40–55 MHz frequency range. The plasma-facing component assembly Faraday screen, comprising beryllium (Be) tile armoured, actively cooled bars located only ~1 cm radially behind innermost point shaped Be first wall panels (FWPs). As such they are close proximity scrape-off layer (SOL) plasma and it important...